TPOP-II: Tritium Fueling at a Reactor Scale

نویسنده

  • P. W. Fisher
چکیده

As part of the International Thermonuclear Experimental Reactor (ITER) plasma fueling development program, Oak Ridge National Laboratory (ORNL) has fabri injection system to test the mechanical and thermal properties of extruded tritium repeating single-stage pneumatic pellet injector, called the Tritium-Proof-of-Principle Phase II (TPOP-II) Pellet Injector, has a piston-driven mechanical extruder and is designed to extrude and accelerate hydrogenic pellets sized for the ITER device. Tritium and D-T pellets have been produced in experiments at the Los Alamos National Laboratory Tritium Systems Test Assembly (TSTA). About 38 g of tritium utilized in the experiment. Two types of runs were made: those in which the material was only extruded and those in which pellets were produced and accelerated with deuterium propellant. These extrusion experiments indicate that both T2 and D-T will require higher extrusion forces than D2 by about a factor of two and that the flow of the material may be characterized by static and dynamic shear strengths. This paper presents results of the TPOP-II extrusion experiments.

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Flibe-Tritium Research for Fission or Fusion Reactors at Kyushu University

There is increasing interest in using ionic molten-salt Flibe not only as self-cooled tritium(T)-breeding material in a fusion reactor blanket but also as fuel solvent of molten-salt fission reactors. Application of Flibe to T-breeding fluid for a stellarator-type fusion reactor operated at a high magnetic field brings large simplification of its blanket structure, allowing continuous operation...

متن کامل

Neutrino masses twenty–five years later

The discovery of neutrino mass marks a turning point in elementary particle physics, with important implications for nuclear and astroparticle physics. Here I give a brief update, where I summarize the current status of three–neutrino oscillation parameters from current solar, atmospheric, reactor and accelerator neutrino data, discuss the case for sterile neutrinos and LSND, and also the impor...

متن کامل

Conceptual design and issue analysis of Laser Fusion Experiment Reactor (LIFT), - Target and Chambers -

We present a conceptual design of a laser fusion experimental reactor (LIFT) and analyze the issues related to the fueling and chamber systems. The LIFT is designed on a scheme of three phases where each phase has specific goals and dedicated chambers driven by the same laser. Based on our understanding, the critical issues include the control of fuel loading in the fueling system and the stabi...

متن کامل

Design of a Multi-Tube Pd-Membrane Module for Tritium Recovery from He in DEMO

Dense self-supported Pd-alloy membranes are used to selectively separate hydrogen and hydrogen isotopes. In particular, deuterium (D) and tritium (T) are currently identified as the main elements for the sustainability of the nuclear fusion reaction aimed at carbon free power generation. In the fusion nuclear reactors, a breeding blanket produces the tritium that is extracted and purified befor...

متن کامل

Tritium Production Analysis and Management Strategies for a Fluoride - salt - cooled High - temperature Test Reactor ( FHTR )

The Fluoride-salt-cooled High-temperature Test Reactor (FHTR) is a test reactor concept that aims to demonstrate the neutronics, thermal-hydraulics, materials, tritium management, and to address other reactor operational and maintenance issues before a commercial Fluoride-salt-cooled High-temperature Reactor (FHR) can be deployed. The MIT Nuclear Systems Design class proposed a design for a 100...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 1998